This study was intended to verify the capability of the Monte Carlo MCNP-4B
code to evaluate spatial dose distribution based on information gathered f
rom CT or SPECT, Methods: A new: three-dimensional (3D) dose calculation ap
proach for internal emitter use in radioimmunotherapy (RIT) was developed u
sing the Monte Carlo MCNP-4B code as the photon and electron transport engi
ne. It was shown that the MCNP-4B computer code can be used with voxel-base
d anatomic and physiologic data to provide 3D dose distributions. Results:
This study showed that the MCNP-4B code can be used to develop a treatment
planning system that will provide such information in a time manner, if dos
e reporting is suitably optimized. If each organ is divided into small regi
ons where the average energy deposition is calculated with a typical volume
of 0.4 cm(3), regional dose distributions can be provided with reasonable
central processing unit times (on the order of 12-24 h on a 200-MHz persona
l computer or modest workstation). Further efforts to provide semiautomated
region identification (segmentation) and improvement of marrow dose calcul
ations are needed to supply a complete system for RIT. It is envisioned tha
t all such efforts will continue to develop and that internal dose calculat
ions may soon be brought to a similar level of accuracy, detail, and robust
ness as is commonly expected in external dose treatment planning. Conclusio
n: For this study we developed a code with a user-friendly interlace that w
orks on several nuclear medicine imaging platforms and provides timely pati
ent-specific dose information to the physician and medical physicist. Futur
e therapy with internal emitters should use a 3D dose calculation approach,
which represents a significant advance over dose information provided by t
he standard geometric phantoms used for more than 20 y (which permit report
ing of only average organ doses for certain standardized individuals)